Event Notification Report for January 09, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/08/2016 - 01/09/2016
Power Reactor
Event Number: 51739
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK TURKAL
HQ OPS Officer: JEFF ROTTON
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK TURKAL
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/17/2016
Notification Time: 10:36 [ET]
Event Date: 01/09/2016
Event Time: 09:46 [EST]
Last Update Date: 02/17/2016
Notification Time: 10:36 [ET]
Event Date: 01/09/2016
Event Time: 09:46 [EST]
Last Update Date: 02/17/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
SHANE SANDAL (R2DO)
SHANE SANDAL (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID ACTUATION OF EMERGENCY DIESEL GENERATOR
"This 60-day optional telephone notification is being made in lieu of an LER submittal, as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of one of the systems listed in 10 CFR 50.73(a)(2)(iv)(B).
"On January 9, 2016, at 0946 Eastern Standard Time (EST), an invalid actuation of EDG 2 occurred. During the performance of procedure 0PT-12.2.1B, 'ECCS D/G #2 Logic Test,' procedure steps were performed out of sequence. As a result, the EDG 2 control logic was not properly defeated to prevent the auto-start prior to testing portions of the Emergency Core Cooling System (ECCS) EDG 2 logic.
"EDG 2 responded properly to the auto-start signal. The actuation was complete, in that the EDG started and ran unloaded. EDG 2 was returned to standby status at 1130 EST. Since no actual bus under voltage condition existed which required the EDG to start, and the start was not in response to actual plant conditions satisfying the requirements for initiation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public."
The licensee has notified the NRC Resident Inspector.
"This 60-day optional telephone notification is being made in lieu of an LER submittal, as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of one of the systems listed in 10 CFR 50.73(a)(2)(iv)(B).
"On January 9, 2016, at 0946 Eastern Standard Time (EST), an invalid actuation of EDG 2 occurred. During the performance of procedure 0PT-12.2.1B, 'ECCS D/G #2 Logic Test,' procedure steps were performed out of sequence. As a result, the EDG 2 control logic was not properly defeated to prevent the auto-start prior to testing portions of the Emergency Core Cooling System (ECCS) EDG 2 logic.
"EDG 2 responded properly to the auto-start signal. The actuation was complete, in that the EDG started and ran unloaded. EDG 2 was returned to standby status at 1130 EST. Since no actual bus under voltage condition existed which required the EDG to start, and the start was not in response to actual plant conditions satisfying the requirements for initiation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 51644
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/09/2016
Notification Time: 07:04 [ET]
Event Date: 01/09/2016
Event Time: 02:37 [CST]
Last Update Date: 01/09/2016
Notification Time: 07:04 [ET]
Event Date: 01/09/2016
Event Time: 02:37 [CST]
Last Update Date: 01/09/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
VIVIAN CAMPBELL (R4DO)
VIVIAN CAMPBELL (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM ON MAIN STEAM ISOLATION DUE TO ELECTRICAL FAULT
"On 1/9/16 at 0237 [CST], River Bend Station sustained a reactor scram during a lightning storm. An electrical transient occurred resulting in a full main steam isolation [MSIV] (Group 6) and a Division II Balance of Plant isolation signal. During the scram, level 8 occurred immediately which tripped the feed pumps. A level 3 signal occurred also during the scram. Subsequent level 3 was received three times due to isolated vessel level control. The plant was stabilized and all spurious isolation signals reset, then the MSIVs were restored. The plant is now stable in Mode 3 and plant walkdowns are occurring to assess the transient."
During the scram, all rods inserted into the core. The plant was initially cooled down using safety relief valves. Offsite power is available and the plant is in its normal shutdown electrical lineup.
The licensee has notified the NRC Resident Inspector.
"On 1/9/16 at 0237 [CST], River Bend Station sustained a reactor scram during a lightning storm. An electrical transient occurred resulting in a full main steam isolation [MSIV] (Group 6) and a Division II Balance of Plant isolation signal. During the scram, level 8 occurred immediately which tripped the feed pumps. A level 3 signal occurred also during the scram. Subsequent level 3 was received three times due to isolated vessel level control. The plant was stabilized and all spurious isolation signals reset, then the MSIVs were restored. The plant is now stable in Mode 3 and plant walkdowns are occurring to assess the transient."
During the scram, all rods inserted into the core. The plant was initially cooled down using safety relief valves. Offsite power is available and the plant is in its normal shutdown electrical lineup.
The licensee has notified the NRC Resident Inspector.